ML20049J991

Proposed Changes to Tech Specs 5.6 & 5.7 Re Spent Fuel Storage Rack Installation.Safety Evaluation Encl

ML20049J991
Person / Time
Site:	Farley
Issue date:	03/19/1982
From:	ALABAMA POWER CO.
To:
Shared Package
ML20049J990	List: ML20049J989 ML20049J991 ML20049J993
References
TAC-48219, NUDOCS 8203290300
Download: ML20049J991 (3)

Text

.. ..

ATTACHMENT 1 DESIGN FEATURES' 5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:

a. AKeff equivalent to less than or equal to 0.95 when flooded with unborated water, which includes conservative allowances for uncer-tainties and biases based on a maximum enrichment of 4.3 weight percent U-235.

b. A nominal 10.75 inch center-to-center distance between fuel assemblies placed in the storage racks.

5.6.1.2 The new fuel pit storage racks are designed and shall be maintained with a nominal 21 inch center-to-center distance between new fuel assemblies such that Keff will 'not exceed 0.98, based on maximum enrichment of 3.5 weight percent U-235, assuming aqueous foam moderation.

DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 149.

CAPACITY 5.6.3 The spent fuel storage pool is designcd and shall be maintained with a storage capacity limited to no more than 1407 fuel assemblies. .

I 5.7 COMP 0NENT CYCLIC OR TRAMSIENT LIMIT 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.

I i

f FARLEY - UNIT 1 5-7 8203290300 spo3,9 l DR ADDCK 05000348 PDR

[

ATTACHMENT 2 SAFETY EVALUATION FOR FARLEY UNIT 1 SPENT FUEL P00L MODIFICATION

Background:

The spent fuel pool at Farley Unit 1 currently contains 13-inch center-to-center spent fuel storage racks. The current spent fuel storage capacity of Unit 1 is 675 fuel assemblies. Alabama Power Company plans to install high density poison spent fuel storage racks at Unit 1. The installation.

of these racks will increase the capacity of the Unit 1 spent fuel pool to 1407 fuel assemblies and require a' revision to the plant technical specifications.

References:

(1) Farley - Unit 1 Technical Specification 5.6.

(2) Joseph M. Farley Nuclear Plant Final Safety Analysis Report.

(3) NRC letter to All Power Reactor Licensees, dated April 14, 1978.

(4) NRC letter to All Power Reactor Licensees, dated January 18, 1979.

(5) Joseph M. Farley Unit 1 Spent Fuel Pool Modification Report.

Bases:

The attached report entitled " Joseph M. Farley Nuclear Plant Unit 1 Spent Fuel Pool Modification" provides the bases for the proposed expansion of the spent fuel pool. lne information provi,ded in this report is consistent with the NRC guidance paper for spent fuel pool modification applications transmitted in References 3 and 4. The report documents the compliance of the Farley - Unit I high density poison spent fuel rack installation with the NRC requirements as specified in the position paper referenced above. ,

The proposed technical specification revisions are provided in Section III l

of this report.

The technical specification revisions were associated with Section 6.6 on Fuel Storage. Paragraphs 5.6.1.1.a and 5.6.1.1.b were revised to incorporate the maximum enrichment and nominal center-to-center distance between fuel assemblies placed in the storage racks.respectively. Paragraph 5.6.1.2 has been deieted because the first core loading has taken place and Alabama Poser Company does not intend to place new fuel in these racks under dry conditioss.

New fuel may be stored in these racks under wet or flooded conditions.

Paragraph 5.6.1.3 has been revised to indicate the maximcm enrichment for the new fuel racks. Additionally, paragraph 5.6.1.3 has been renumbered to 5.6.1.2.

l i

t

r

. . . .= -

Paragraph 5.6.3.has been revised to increase the capacity of the spent fuel pool from 675 to 1407 fuel assemblies. The bases for the above changes are documented in Reference (5).

1

Conclusion:

f The proposed expansion of the spent fuel pool and change to Section 5.6 3

of the technical specifications do not involve an unreviewed safety question as defined by 10CFR50.59.

4 i

I

's e

i

AllACHMENT l

l l

. . , - . - . _ . - - . ..-. - - -- - - - - - - -